Improving the Neutronic Characteristics of a Boiling Water Reactor by Using Uranium Zirconium Hydride Fuel Instead of Uranium Dioxide Fuel

Improving the Neutronic Characteristics of a Boiling Water Reactor by Using Uranium Zirconium Hydride Fuel Instead of Uranium Dioxide Fuel

The present work discusses two different models of boiling water reactor (BWR) bundle to compare the neutronic characteristics of uranium dioxide (UO2) and uranium zirconium hydride (UZrH1.6) fuel. Each bundle consists of four assemblies. The BWR assembly fueled with UO2 contains 8 × 8 fuel rods whi...

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Bibliographic Details
Main Author: Ahmed Abdelghafar Galahom
Format: Article
Language:English
Published: Elsevier 2016-06-01
Series:Nuclear Engineering and Technology
Subjects:
BWR
Normalized Power
Reactivity effect of voiding
Thermal Neutron flux
Uranium Dioxide
Uranium Zirconium Hydride
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573316000103

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http://www.sciencedirect.com/science/article/pii/S1738573316000103

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